US6163588A - Core plate and reactor internal pump differential pressure lines for a boiling water reactor - Google Patents

Core plate and reactor internal pump differential pressure lines for a boiling water reactor Download PDF

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Publication number
US6163588A
US6163588A US09/219,968 US21996898A US6163588A US 6163588 A US6163588 A US 6163588A US 21996898 A US21996898 A US 21996898A US 6163588 A US6163588 A US 6163588A
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United States
Prior art keywords
section
shroud
pressure line
bottom head
pressure
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Expired - Fee Related
Application number
US09/219,968
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English (en)
Inventor
Jack T. Matsumoto
Alex B. Fife
Gary J. Ballas
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General Electric Co
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General Electric Co
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Priority to US09/219,968 priority Critical patent/US6163588A/en
Assigned to GENERAL ELECTRIC COMPANY reassignment GENERAL ELECTRIC COMPANY ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: BALLAS, GARY J., FIFE, ALEX B., MATSUMOTO, JACK T.
Priority to JP33911299A priority patent/JP4656684B2/ja
Priority to TW088121564A priority patent/TW444204B/zh
Priority to DE69928762T priority patent/DE69928762T2/de
Priority to EP99310450A priority patent/EP1022748B1/de
Priority to CN99126904A priority patent/CN1260570A/zh
Application granted granted Critical
Publication of US6163588A publication Critical patent/US6163588A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/10—Means for supporting the complete structure
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates generally to nuclear reactors and more particularly, to core plate and reactor internal pump differential pressure lines for a boiling water reactor.
  • a reactor pressure vessel (RPV) of a boiling water reactor (BWR) typically has a generally cylindrical shape and is closed at both ends, e.g., by a bottom head and a removable top head.
  • a top guide typically is spaced above a core plate within the RPV.
  • a core shroud, or shroud typically surrounds the core plate and is supported by a shroud support structure. Particularly, the shroud has a generally cylindrical shape and surrounds both the core plate and the top guide.
  • the core center axis is substantially coaxial with the center axis of the shroud, and the shroud is open at both ends so that water can flow up through the lower end of the shroud and out through the upper end of the shroud.
  • the shroud, top guide, and core plate limit lateral movement of the core fuel bundles.
  • the shroud due to its large size, is formed by coupling a plurality of stainless steel cylindrical sections together, typically by welding.
  • Shroud welds increase the susceptibility of the shroud material to a detrimental effect known as inter-granular stress corrosion cracking (IGSCC).
  • IGSCC inter-granular stress corrosion cracking
  • cracking may occur in the heat affected zone of the shroud welds.
  • volumetric inspections are performed to detect and evaluate the extent of cracking. If the cracking is determined to be significant, repairs may be performed to re-establish the integrity of the weld joint, or the shroud is replaced.
  • the RPV also includes reactor internal pumps located in the annulus between the shroud and the pressure vessel wall.
  • the internal pumps provide circulation of water in the RPV.
  • differential pressure lines are used to measure the reactor internal pump flow and the flow of water through the reactor core located inside the shroud.
  • the pressure lines are usually constructed using pipe and pipe fittings.
  • the pressure lines enter the RPV through penetrations in the bottom head.
  • the pressure lines extend along the inside of the shroud and are supported by brackets welded to the shroud. The brackets are required to prevent flow induced vibrations in the pressure lines.
  • One reactor internal pump differential pressure line penetrates the shroud above pump impellers and the other terminates below the impellers inside of the shroud.
  • the core differential pressure lines terminate above and below the core plate.
  • differential lines are welded to the shroud, replacement of shroud sections is difficult and time consuming.
  • the pressure lines must first be removed from the shroud section before replacement of the shroud section.
  • the differential pressure lines must be reinstalled, i.e., welded to the new shroud section.
  • a modular differential pressure measuring system for a boiling water nuclear reactor pressure vessel.
  • the differential pressure measuring system permits the use of replaceable shroud sections because the modular pressure system does not require cutting the pressure lines or pressure line supports for replacement of the replaceable shroud sections. Additionally, the modular differential pressure system does not require welding of pressure lines and/or pressure line supports during installation of a replaceable shroud section.
  • the modular differential pressure system includes a plurality of pressure lines with each pressure line including a plurality of pressure line sections.
  • the modular system also includes a shroud having at least one replaceable shroud section.
  • Each shroud section includes at least one pressure line section configured to connect to and disconnect from corresponding pressure line sections in adjacent shroud sections without welding.
  • a shroud section may include at least one pressure line coupled to support brackets welded to the shroud section. The pressure line remains coupled to the shroud section and is removed or installed with the shroud section as a modular component. Connections of the pressure lines of one shroud section to an adjacent section are located at the flanged interface between shroud sections. Therefore, a separate flanged joint for the pressure line sections are not required, and welding of the connection is also not required.
  • the modular system also includes a reactor bottom head petal section.
  • the bottom head petal section is configured to support the shroud sections and includes a shroud support flange.
  • the bottom head petal section also includes a plurality of bores defining pressure line sections. At least one pressure line section of the bottom head petal is configured to couple with a corresponding pressure line section of an adjacent shroud section.
  • a short vertical bore extends from the end of the horizontal bore to an outside surface of the shroud support flange. This vertical bore is configured to couple to a vertical bore in the lower shroud section, sometimes referred to as the shroud support.
  • the vertical bore may extend vertically through several shroud sections, or the lower shroud vertical bore may include a short horizontal bore extending from the end of the bore to an outside surface of the lower shroud section.
  • This horizontal bore may in turn be coupled to a vertical or horizontal pipe section of the pressure line extending along the inside surface of the shroud.
  • the modular differential pressure system measures the pressure at two separate points within the reactor pressure vessel.
  • the pressure differential is an indication of the flow between the two points within the reactor.
  • the core flow is measured by measuring the pressure above and below the reactor core plate.
  • the flow in the annulus of the reactor may be measured by measuring the pressure above and below the reactor internal pump impellers.
  • the pressure system is modular, when a shroud section is removed for replacement, the modular pressure lines are removed with the shroud section. No cutting is required to disconnect a pressure line section from the corresponding pressure line section of an adjacent shroud section. The removed shroud section is then replaced with a shroud section that also includes integral pressure lines which re-couple to the pressure lines of an adjacent shroud section without welding.
  • the above described modular differential pressure system permits the replacement of shroud sections without having to cut the differential pressure lines from the shroud.
  • the modular differential pressure system also permits the installation of a replacement shroud section without having to reinstall the pressure lines by welding the lines to the core shroud.
  • the modular system also simplifies and speeds up the process of replacing the core shroud in a nuclear reactor.
  • FIG. 1 is a sectional view, with parts cut away, of a boiling water nuclear reactor pressure vessel.
  • FIG. 2 is a partial sectional view of an RPV having a reactor core shroud in accordance with an embodiment of the present invention.
  • FIG. 3 is a partial sectional view of an RPV having a reactor core shroud in accordance with an embodiment of the present invention.
  • FIG. 4 is a partial sectional view of an RPV having a reactor core shroud in accordance with an embodiment of the present invention.
  • FIG. 5 is a partial sectional view of an RPV having a reactor core shroud in accordance with an embodiment of the present invention.
  • FIG. 6 is a partial sectional view of an RPV having a reactor core shroud in accordance with another embodiment of the present invention.
  • FIG. 7 is a partial sectional view of an RPV having a reactor core shroud in accordance with another embodiment of the present invention.
  • FIG. 8 is a partial sectional view of an RPV having a reactor core shroud in accordance with another embodiment of the present invention.
  • FIG. 9 is a partial sectional view of an RPV having a reactor core shroud in accordance with another embodiment of the present invention.
  • FIG. 1 is a sectional view, with parts cut away, of a nuclear reactor pressure vessel (RPV) 10.
  • RPV 10 has a generally cylindrical shape and is closed at one end by a bottom head 12 and at its other end by a removable top head (not shown).
  • a bottom head petal 14 extends from the bottom head and supports the side wall (not shown) of RPV 10.
  • a cylindrically shaped core shroud 16 surrounds the reactor core (not shown) and is supported by a shroud support 18.
  • An annulus 20 is formed between shroud 16 and the sidewall of RPV 10.
  • Baffle plate 22 includes a plurality of circular openings 24 that house reactor internal pump impellers 26. Reactor internal pump impellers 26 cause the water in RPV 10 to flow through annulus 20.
  • Shroud 16 is formed by a lower shroud section 28 and an upper shroud section 30.
  • a circular core plate ledge 32 is located between upper and lower shroud sections 28 and 30.
  • RPV 10 also includes a core plate 34 coupled to core plate ledge 32.
  • RPV 10 includes core flow differential pressure lines 36 (one shown). Differential pressure lines 36 enter RPV 10 through bottom head 12 and extend vertically along the inside of shroud 16. Differential pressure lines 36 are coupled to shroud 16 by a plurality of support brackets 38. Particularly, brackets 38 are welded to shroud 16 and differential pressure lines 36 are welded to support brackets 38. Additionally, reactor internal pump flow may be measured by measuring the differential pressure at a location above and below reactor internal pump impellers 26. RPV 10 also includes reactor internal pump flow differential pressure lines 40 (one shown).
  • Differential pressure lines 40 enter RPV 10 through bottom head 12 and extend vertically along the inside of shroud 16. Differential pressure lines 40 also extend horizontally along the inside of shroud 16 to a point above or below reactor internal pump impeller 26. Like differential pressure lines 36, differential lines 40 are coupled to shroud 16 by support brackets 38. Differential pressure lines 36 and 40 are typically of welded construction using pipe and pipe fittings.
  • FIGS. 2, 3, 4, and 5 are partial sectional views of an RPV 50 having a reactor core shroud 52 in accordance with an embodiment of the present invention.
  • RPV 50 includes a bottom head petal 54 having a shroud support flange 56.
  • RPV sidewall 58 extends from bottom head petal 54.
  • Shroud 52 is supported by shroud support flange 56 of bottom head petal 54.
  • Shroud 52 includes a first shroud section 60, typically referred to as the flange, a second shroud section 62, typically referred to as the lower shroud, and a third shroud section 64, typically referred to as the upper shroud.
  • a core plate ledge 66 is located between second and third shroud sections 62 and 64.
  • a core plate 68 is coupled to core plate ledge 66.
  • differential pressure line 70 includes first, second, third, and fourth pressure line sections 74, 76, 78, and 80.
  • First pressure line section 74 is defined by a bore 82 extending from an outer surface 84 of bottom head petal 54 to an outer surface 86 of shroud support flange 56.
  • Second pressure line section 76 is defined by a first bore 88 extending from a flange mating surface 90 of first shroud section 60 and a second bore 92 extending substantially perpendicularly from an end 94 of first bore 88 to an inside surface 96 of shroud 52.
  • Second pressure line section 76 is configured to couple to first pressure line section 74.
  • Third pressure line section 78 is defined by a pipe 98 extending toward core plate 68 along inner surface 96 of shroud 52. Pipe 98 is coupled to shroud 52 by support brackets 100. Third pressure line section 78 is configured to couple to second pressure line section 76 and fourth pressure line section 80.
  • Fourth pressure line section 80 is defined by a first bore 102 extending into second shroud section 62, a second bore 104 extending substantially perpendicularly from an end 106 of first bore 102 through second shroud section 62, through core plate ledge 66, and into third shroud section 64, and a third bore 108 extending substantially perpendicularly from an end 110 of second bore 104 to an inside surface 112 of third shroud section 64.
  • differential pressure line 72 includes first, second, and third pressure line sections 114, 116, and 118.
  • First pressure line section 114 is defined by a bore 120 extending from outer surface 84 of bottom head petal 54 to outer surface 86 of shroud support flange 56.
  • Second pressure line section 116 is defined by a first bore 122 extending from flange mating surface 90 of first shroud section 60 and a second bore 124 extending substantially perpendicularly from an end 126 of first bore 122 to inside surface 96 of shroud 52.
  • Second pressure line section 116 is configured to couple to first pressure line section 114.
  • Third pressure line section 118 is defined by a pipe 126 extending toward core plate 68 along inner surface 96 of shroud 52 and terminating below core plate 68. Pipe 126 is coupled to shroud 52 by support brackets 100.
  • differential pressure line 128 includes first and second pressure line sections 132 and 134.
  • First pressure line section 132 is defined by a bore 136 extending from outer surface 84 of bottom head petal 54 to an inner surface 138 of bottom head petal 54.
  • Second pressure line section 134 is defined by a pipe 140 coupled to bore 136 and terminating adjacent shroud support flange 56 opposite: to surface 86.
  • differential pressure line 130 includes first, second, third, and fourth pressure line sections 142, 144, 146, and 148.
  • First pressure line section 142 is defined by a bore 150 extending from outer surface 84 of bottom head petal 54 to outer surface 186 of shroud support flange 56.
  • Second pressure line section 144 is defined by a first bore 152 extending from a flange mating surface 90 of first shroud section 60 and a second bore 154 extending substantially perpendicularly from an end 153 of first bore 152 to inside surface 96 of shroud 52. Second pressure line section 144 is configured to couple to first pressure line section 142.
  • Third pressure line section 146 is defined by a pipe 156 extending toward core plate 68 along inner surface 96 of shroud 52. Pipe 156 is coupled to shroud 52 by support brackets 100. Third pressure line section is configured to couple to second pressure line section 144 and fourth pressure line section 148. Fourth pressure line section 148 is defined by a bore 158 extending through second shroud section 62.
  • modular differential pressure lines 70, 72, 128, and 130 measure the pressure at separate points within the reactor pressure vessel.
  • the pressure differential is an indication of the flow between two points within the reactor.
  • the core flow is measured by measuring the pressure above and below reactor core plate 68 by differential pressure lines 70 and 72.
  • the flow in the annulus of the reactor may be measured by measuring the pressure above and below the reactor internal pump impellers by differential pressure lines 128 and 130.
  • pressure lines 70, 72, 128, and 130 are modular, when a shroud section such as shroud section 60, 62, or 64 is removed for replacement, the modular pressure line sections or portions of those sections that are integral to the shroud section are removed with the shroud section. For example, if shroud section 64 was removed from reactor 50, the portions of integral pressure line section 80 that are associated with shroud section 64 would also be removed, i.e., second bore 104 and third bore 108. No cutting is required to disconnect a pressure line section from the corresponding pressure line section of an adjacent shroud section. The removed shroud section is then replaced with a shroud section that also includes integral pressure lines which re-couple to the pressure lines of an adjacent shroud section without welding.
  • the above described modular differential pressure lines 70, 72, 128, and 130 permit the replacement of shroud sections 60, 62, and 64 without having to cut the differential pressure lines from the shroud.
  • the modular differential pressure lines also permit the installation of a replacement shroud section without having to reinstall the pressure lines by welding the lines to core shroud 52.
  • the modular differential pressure lines also simplify and speed up the process of replacing core shroud 52 in reactor pressure vessel 50.
  • FIGS. 6, 7, 8, and 9 are sectional views of an RPV 200 having a reactor core shroud 202 in accordance with another embodiment of the present invention.
  • RPV 200 includes a bottom head petal 204 having a shroud support flange 206.
  • RPV sidewall 208 extends from bottom head petal 204.
  • Shroud 202 is supported by shroud support flange 206 of bottom head petal 204.
  • Shroud 202 includes a first shroud section 210, typically referred to as the shroud support, a second shroud section 212, typically referred to as the lower shroud, and a third shroud section 214, typically referred to as the upper shroud.
  • a core plate ledge 216 is locate between second and third shroud sections 212 and 214.
  • a core plate 218 is coupled to core plate ledge 216.
  • RPV 200 includes modular differential pressure lines 220 (FIG. 6) and 222 (FIG. 7).
  • differential pressure line 220 includes first and second pressure line sections 224 and 226.
  • First pressure line section 224 is defined by a bore 228 extending from an outer surface 230 of bottom head petal 204 to an outer surface 232 of shroud support flange 206.
  • Second pressure line section 226 is defined by a first bore 234 extending from a flange mating surface 236 of first shroud section 210 through first shroud section 210, through second shroud section 212, through core plate ledge 216, and into third shroud section 214, and a second bore 238 extending substantially perpendicularly from an end 239 of first bore 234 to an inside surface 240 of shroud 202. Second pressure line section 226 is configured to couple to first pressure line section 224.
  • differential pressure line 222 includes first and second pressure line sections 242 and 244.
  • First pressure line section 242 is defined by a bore 246 extending from outer surface 230 of bottom head petal 204 to an outer surface 232 of shroud support flange 206.
  • Second pressure line section 244 is defined by a first bore 248 extending from a flange mating surface 236 of first shroud section 210 through first shroud section 210, through second shroud section 212, and into core plate ledge 216, and a second bore 250 extending substantially perpendicularly from an end 252 of first bore 248 to an inside surface 254 of core plate ledge 216.
  • Second pressure line section 244 is configured to couple to first pressure line section 242.
  • differential pressure line 256 includes first and second pressure line sections 260 and 262.
  • First pressure line section 260 is defined by a bore 264 extending from outer surface 230 of bottom head petal 204 to an inner surface 266 of bottom head petal 204.
  • Second pressure line section 262 is defined by a pipe 268 coupled to bore 264 and terminating adjacent shroud support flange 206 and opposite to surface 232.
  • differential pressure line 258 includes first, second, third, and fourth pressure line sections 270, 272, 274 and 276.
  • First pressure line section 270 is defined by a bore 278 extending from outer surface 230 of bottom head petal 204 to outer surface 232 of shroud support flange 206.
  • Second pressure line section 272 is defined by a first bore 280 extending from flange mating surface 236 of first shroud section 210, through first shroud section 210 and into second shroud section 212, and a second bore 282 extending substantially perpendicularly from an end 284 of first bore 280 to inside surface 240 of shroud 202.
  • Second pressure line section 272 is configured to couple to first pressure line section 270.
  • Third pressure line section 274 is defined by a pipe 286 extending toward core plate 218 along inner surface 236 of shroud 202. Third pressure line section 274 is configured to couple to second pressure line section 272 and fourth pressure line section 276. Fourth pressure line section 276 is defined by a bore 288 extending through second shroud section 212.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US09/219,968 1998-12-23 1998-12-23 Core plate and reactor internal pump differential pressure lines for a boiling water reactor Expired - Fee Related US6163588A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
US09/219,968 US6163588A (en) 1998-12-23 1998-12-23 Core plate and reactor internal pump differential pressure lines for a boiling water reactor
JP33911299A JP4656684B2 (ja) 1998-12-23 1999-11-30 沸騰水型原子炉の原子炉圧力容器用のモジュール式シュラウドシステム及び該モジュール式シュラウドシステムを有するモジュール式差圧測定システム
TW088121564A TW444204B (en) 1998-12-23 1999-12-09 Core plate and reactor internal pump differential pressure lines for a boiling water reactor
DE69928762T DE69928762T2 (de) 1998-12-23 1999-12-22 Modulares Hüllsystem für einen Druckbehälter eines Kernreaktors
EP99310450A EP1022748B1 (de) 1998-12-23 1999-12-22 Modulares Hüllsystem für einen Druckbehälter eines Kernreaktors
CN99126904A CN1260570A (zh) 1998-12-23 1999-12-23 沸水堆的堆芯板和反应堆内泵压差管线

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Application Number Priority Date Filing Date Title
US09/219,968 US6163588A (en) 1998-12-23 1998-12-23 Core plate and reactor internal pump differential pressure lines for a boiling water reactor

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US6163588A true US6163588A (en) 2000-12-19

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US09/219,968 Expired - Fee Related US6163588A (en) 1998-12-23 1998-12-23 Core plate and reactor internal pump differential pressure lines for a boiling water reactor

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US (1) US6163588A (de)
EP (1) EP1022748B1 (de)
JP (1) JP4656684B2 (de)
CN (1) CN1260570A (de)
DE (1) DE69928762T2 (de)
TW (1) TW444204B (de)

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6504888B1 (en) * 1999-12-23 2003-01-07 General Electric Company Apparatus and methods of flow measurement for a boiling water reactor internal pump
US6782886B2 (en) 1995-04-05 2004-08-31 Aerogen, Inc. Metering pumps for an aerosolizer
US20080247498A1 (en) * 2007-04-09 2008-10-09 Fred Charles Nopwaskey Methods and apparatuses for operating and repairing nuclear reactors
US7677467B2 (en) 2002-01-07 2010-03-16 Novartis Pharma Ag Methods and devices for aerosolizing medicament
US7748377B2 (en) 2000-05-05 2010-07-06 Novartis Ag Methods and systems for operating an aerosol generator
US7771642B2 (en) 2002-05-20 2010-08-10 Novartis Ag Methods of making an apparatus for providing aerosol for medical treatment
US7946291B2 (en) 2004-04-20 2011-05-24 Novartis Ag Ventilation systems and methods employing aerosol generators
US7971588B2 (en) 2000-05-05 2011-07-05 Novartis Ag Methods and systems for operating an aerosol generator
US8336545B2 (en) 2000-05-05 2012-12-25 Novartis Pharma Ag Methods and systems for operating an aerosol generator
US8398001B2 (en) 1999-09-09 2013-03-19 Novartis Ag Aperture plate and methods for its construction and use
US8539944B2 (en) 2002-01-07 2013-09-24 Novartis Ag Devices and methods for nebulizing fluids for inhalation
US8561604B2 (en) 1995-04-05 2013-10-22 Novartis Ag Liquid dispensing apparatus and methods
US8616195B2 (en) 2003-07-18 2013-12-31 Novartis Ag Nebuliser for the production of aerosolized medication
US9108211B2 (en) 2005-05-25 2015-08-18 Nektar Therapeutics Vibration systems and methods

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Publication number Priority date Publication date Assignee Title
KR101385895B1 (ko) * 2007-01-02 2014-04-15 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 원자로 정렬판 구조체
CN105719707A (zh) * 2014-12-01 2016-06-29 上海核工程研究设计院 压水反应堆整体水力模拟试验中的压差测点布置结构
WO2023135724A1 (ja) * 2022-01-14 2023-07-20 日立Ｇｅニュークリア・エナジー株式会社 原子炉の炉内配管構造

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5615239A (en) * 1995-11-17 1997-03-25 General Electric Company Core differential pressure and liquid control line apparatus in a nuclear reactor

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5786788A (en) * 1980-11-20 1982-05-29 Hitachi Ltd Nuclear reactor with built-in coolant recirculation pump
JPS58129293A (ja) * 1982-01-27 1983-08-02 株式会社日立製作所 冷却材流量測定装置
JPS5988688A (ja) * 1982-11-12 1984-05-22 株式会社東芝 原子炉内差圧検出装置
JPS62184393A (ja) * 1986-02-10 1987-08-12 株式会社東芝 ジエツトポンプ計測配管取付装置
EP0383628B1 (de) * 1989-02-17 1994-09-21 Kabushiki Kaisha Toshiba Gerät zur Messung von Kühlmitteldurchflussmengen und zur Kraftsteuerung in einem Siedewasserreactor
JPH05150078A (ja) * 1991-11-27 1993-06-18 Toshiba Corp 沸騰水型原子炉
JP2521390B2 (ja) * 1992-03-16 1996-08-07 株式会社日立製作所 パイプホイップストラクチャの据付け方法
JP3269728B2 (ja) * 1994-02-25 2002-04-02 株式会社日立製作所 ジェットポンプ計測管固定用クランプ
JPH07287090A (ja) * 1994-04-20 1995-10-31 Hitachi Ltd 原子炉用炉内構造物
FR2724484B1 (fr) * 1994-09-09 1996-12-13 Framatome Sa Dispositif d'etancheite pour une colonne d'instrumentation traversant le couvercle de la cuve d'un reacteur nucleaire a l'interieur d'un adaptateur
JPH08248176A (ja) * 1995-03-13 1996-09-27 Ishikawajima Harima Heavy Ind Co Ltd 原子炉圧力容器の差圧検出管取付け構造
JPH09133780A (ja) * 1995-11-07 1997-05-20 Toshiba Eng Co Ltd シュラウド付属構造物の据付構造

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5615239A (en) * 1995-11-17 1997-03-25 General Electric Company Core differential pressure and liquid control line apparatus in a nuclear reactor

Cited By (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6782886B2 (en) 1995-04-05 2004-08-31 Aerogen, Inc. Metering pumps for an aerosolizer
US8561604B2 (en) 1995-04-05 2013-10-22 Novartis Ag Liquid dispensing apparatus and methods
US8398001B2 (en) 1999-09-09 2013-03-19 Novartis Ag Aperture plate and methods for its construction and use
US6504888B1 (en) * 1999-12-23 2003-01-07 General Electric Company Apparatus and methods of flow measurement for a boiling water reactor internal pump
US7748377B2 (en) 2000-05-05 2010-07-06 Novartis Ag Methods and systems for operating an aerosol generator
US7971588B2 (en) 2000-05-05 2011-07-05 Novartis Ag Methods and systems for operating an aerosol generator
US8336545B2 (en) 2000-05-05 2012-12-25 Novartis Pharma Ag Methods and systems for operating an aerosol generator
US8196573B2 (en) 2001-03-20 2012-06-12 Novartis Ag Methods and systems for operating an aerosol generator
US7677467B2 (en) 2002-01-07 2010-03-16 Novartis Pharma Ag Methods and devices for aerosolizing medicament
US8539944B2 (en) 2002-01-07 2013-09-24 Novartis Ag Devices and methods for nebulizing fluids for inhalation
US7771642B2 (en) 2002-05-20 2010-08-10 Novartis Ag Methods of making an apparatus for providing aerosol for medical treatment
US8616195B2 (en) 2003-07-18 2013-12-31 Novartis Ag Nebuliser for the production of aerosolized medication
US7946291B2 (en) 2004-04-20 2011-05-24 Novartis Ag Ventilation systems and methods employing aerosol generators
US9108211B2 (en) 2005-05-25 2015-08-18 Nektar Therapeutics Vibration systems and methods
US20080247498A1 (en) * 2007-04-09 2008-10-09 Fred Charles Nopwaskey Methods and apparatuses for operating and repairing nuclear reactors
US20140098921A1 (en) * 2007-04-09 2014-04-10 Global Nuclear Fuels - Americas, Llc Methods and apparatuses for operating and repairing nuclear reactors
US9959943B2 (en) * 2007-04-09 2018-05-01 General Electric Company Method and apparatuses for operating and repairing nuclear reactors

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EP1022748A1 (de) 2000-07-26
CN1260570A (zh) 2000-07-19
DE69928762T2 (de) 2006-09-07
JP4656684B2 (ja) 2011-03-23
JP2000206285A (ja) 2000-07-28
DE69928762D1 (de) 2006-01-12
EP1022748B1 (de) 2005-12-07
TW444204B (en) 2001-07-01

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